Estimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA condition
Autor: | J.L. Singh, Suparna Banerjee, J.S. Dubey, Baidyanath Rath, Sunil Kumar, Tapan K. Sawarn, Vivek Bhasin, R.S. Shriwastaw |
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Rok vydání: | 2017 |
Předmět: |
010302 applied physics
Quenching Cladding (metalworking) Nuclear and High Energy Physics Materials science Metallurgy Zirconium alloy 02 engineering and technology 021001 nanoscience & nanotechnology Microstructure 01 natural sciences Nuclear Energy and Engineering 0103 physical sciences Ultimate tensile strength General Materials Science Limiting oxygen concentration 0210 nano-technology Ductility Tensile testing |
Zdroj: | Journal of Nuclear Materials. 493:460-470 |
ISSN: | 0022-3115 |
DOI: | 10.1016/j.jnucmat.2017.06.032 |
Popis: | The present study involves the estimation of ring tensile properties of Indian Pressurised Heavy Water Reactor (IPHWR) fuel cladding made of Zircaloy-4, subjected to experiments under a simulated loss-of-coolant-accident (LOCA) condition. Isothermal steam oxidation experiments were conducted on clad tube specimens at temperatures ranging from 900 to 1200 °C at an interval of 50 °C for different soaking periods with subsequent quenching in water at ambient temperature. The specimens, which survived quenching, were then subjected to ambient temperature ring tension test (RTT). The microstructure was correlated with the mechanical properties. The yield strength (YS) and ultimate tensile strength (UTS) increased initially with rise in oxidation temperature and time duration but then decreased with further increase in oxidation. Ductility is adversely affected with rising oxidation temperature and longer holding time. A higher fraction of load bearing phase and lower oxygen content in it ensures higher residual ductility. Cladding shows almost zero ductility behavior in RIT when load bearing phase fraction is less than 0.72 and its average oxygen concentration is greater than 0.58 wt%. |
Databáze: | OpenAIRE |
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